ML19345A581
| ML19345A581 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 04/15/1968 |
| From: | Skovholt D US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19345A579 | List: |
| References | |
| NUDOCS 8011240236 | |
| Download: ML19345A581 (3) | |
Text
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!%.A SAFE'IY EVALUATION BY 'IHE DIVISION OF REACTOR LICENSING DOCKET NO. 50-29 IN THE MKITER OF YANKEE A'IGMIC ELECTRIC TMPANY i
PROPOSED WANGE NO. 82 INTRODUCTION By letters dated January 12, 1968 and Kirch 12, 1968, Yankee Atomic Electric Company, in Proposed Change No. 82, mquested authorization of three changes in the Technical Specifications of License No. DPR-3.
'Ihe proposed changes would authorize installation of instrurentation and wiring to increase the reliability of the Safety Injection System and a valve in the Charging and Volume Control System to reduce the likelihood of loss of primry system coolant. Supplemental information was submitted by letter dated March 20, 1968.
DISCUSSION The licensee proposes during the next refueling operation to install the following:
1.
Independent instrumentation to provide a secnnd reactor coolant pressure signal to automtically iritiate safety injection of boric acid in the event of low-pressure condition in the reactor coolant system; 2.
A duplica.e automatic safety injection circuit, so that in the event of a signal from either the present reactor-coolant pressure channel or from the new pressure channel to be installed, the boric acid Safety Injection System will fu ction.
3.
A new 2-inch check valve in the charging line as near as practical (approximtely 3 feet) to the reactor coolant pipe.
At present there is only one channel which provides the pressure signal that initiates automatic safety injection of boric acid into the reactor. 'Ihe pressure sensor, installed on the reactor coolant pipe, feeds a bistable trip device. 'Ihe proposed pressure sensor to be installed on the pressurizer will be of the bourdon type. 'Ihe new pressure sensor will have a completely independent circuit.
A low-pressure signal from either ch inel will actuate the Safety Injection System.
We agree with the licensee's opinion that installation of a second independent pressure channel will increase the reliability of initiating the Safety Injecticn System in the event of low pressure in the reactor coolant system without reducing safety.
Bonn.o 93 6 m
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The pmposed 2-inch check valve to be installed in the charging line should reduce the likelihood of loss of primary system coolant in case of a failure between the pmsent check valve and the pmposed new one. The pmsent check valve is located near the containnent vessel; the pmposed valve will be in-stalled as close to the reactor coolant pipe as practical. In our opird.cn, the installation of an additional check valve in the charging line does itot present any new hazards.
The licensee also states that the 3-foot section between the new check valve and the reactor coolant pipe will be inspected by dye penetrant tests at each~
mfueling; this inspection will pmvide added assurance of its integrity.
CONCLUSION On the basis of the foregoing considerations, we have concluded that the pm-posed changes to the facilitydo not present significant hazards considerations not described or implicit in the hazards sumary mport, and that them is reasonable assurance that the health and safety of the public will rot be endangered.
/?f Donald J.
ovholt-i I
- Assistant Dimetor for Reactor Operations Division of Reactor Licensing.
Date:
April 15, 1968 l
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